Issue 99: RCS/RHR Suction Line Valve Interlock on PWRs
DESCRIPTION
Historical Background
On April 17, 1984, a DSI memorandum[1]on the subject of RHR interlocks for W plants d
On April 17, 1984, a DSI memorandum[1]on the subject of RHR interlocks for W plants d
During the review of LaSalle, ASB identified a potential problem which could be generic to all BWRs.[1]
Over the past several years, the NRC staff has noted an unacceptably large number of overexposures and uncontrolled exposures associated with pressurized water reactor cavity entries
This issue was identified during the staff review of the Indian Point 2 and Zion PRAs[1]; in
This concern was raised by an NRC resident inspector who questioned the practice of leaving the refueling canal
Low temperature overpressurization originally identified in NUREG 0371[1]as item A-26.
This issue was recommended[1]for prioritization by DSI after a review of the AEOD engineerin
Experiments conducted at several test facilities prior to 1984 showed that irradiated fuel can fragment (crumble) into small pieces during a LOCA.
On August 12, 1983, one of the three emergency diesel generators (EDG) at the Shoreham Plant failed during overload testing as a result of a fractured c
Reactor protection systems (RPS) or "scram" systems are tripped by many diverse signals.